ENTRY 40587 20090416 41464058700000001 SUBENT 40587001 20090416 41464058700100001 BIB 16 63 4058700100002 INSTITUTE (4UKRIJD) 4058700100003 REFERENCE (C,80KIEV,2,257,198009) 4058700100004 (C,77KIEV,2,252,197704) Experimental details 4058700100005 AUTHOR (A.V.Murzin, A.F.Rudyk, V.A.Libman) 4058700100006 TITLE measurement of the fission cross-section for 4058700100007 U-233 and U-235 at the neutron energy 24.5 keV 4058700100008 FACILITY (REAC) VBR-M 4058700100009 INC-SOURCE (REAC) Quasimonoenergetic neutrons were obtained by 4058700100010 means of the interference filters, consisted of 4058700100011 iron 195 gram/cm**2, aluminum 95 gram/cm**2, 4058700100012 sulphur 13 gram/cm**2 . 4058700100013 Collimators system of 3600 mm length, output diameter 4058700100014 24 mm. 4058700100015 INC-SPECT In incident neutron spectrum there were the neutrons 4058700100016 of energies 72, 133, 279, 357 keV - 3.6% of 24.5 keV 4058700100017 neutrons. 4058700100018 24.5 keV neutron beam - 2.E+5 n/cm**2/sec . 4058700100019 Additional Ti filter of 7.1 g/cm**2 to define 4058700100020 neutrons of energy > 24.5 keV. 4058700100021 METHOD (TRN) Thermal neutron transmission was measured by 4058700100022 Ge(Li) detector and "black" B-10 sample : 4058700100023 for U-233 - 0.232 (+-0.8%), 4058700100024 for U-235 - 0.244 (+-0.6%) . 4058700100025 DETECTOR (SCIN) Stilbene scintillation detector. 4058700100026 For U-233 measurement - crystal of 30mm diameter, 4058700100027 20 mm length. 4058700100028 For U-235 measurement - crystal of 40mm diameter, 4058700100029 40 mm length. 4058700100030 Cf-252 source was used for neutron registration 4058700100031 efficiency control. 4058700100032 (PROPC) Hydrogen proportional counter SNM-38 for 4058700100033 neutron spectrum measurement after filters. 4058700100034 (GELI) Ge(Li) detector of about 40 cm**3 for neutron 4058700100035 beam measurement via reaction B-10(n,A+G)Li-7 on B-10 4058700100036 sample of 0.11 g/cm**2 , 28.35 mm diameter. 4058700100037 Calibration of registration efficiency of stilbene and4058700100038 Ge(Li) detectors were made in thermal neutron beam with4058700100039 the same samples. 4058700100040 MONITOR ((MONIT1)5-B-10(N,G+A)3-LI-7,,SIG) at 24.5 keV. 4058700100041 ((MONIT2)(5-B-10(N,A)3-LI-7,,SIG)/(5-B-10(N,TOT),,SIG))4058700100042 at thermal energy. 4058700100043 MONIT-REF ((MONIT1),,R,BNL-NCS-50496,1975) ENDF-B/IV . 4058700100044 ((MONIT2),,R,BNL-NCS-50496,1975) ENDF-B/IV . 4058700100045 PART-DET (N) Fission neutrons 4058700100046 HISTORY (19810511C) 4058700100047 (19851003U) 4058700100048 (20090416A) M.M. BIB and COMMON information was added. 4058700100049 Free text was corrected to be human-readable. 4058700100050 Dates were corrected for 4-digits year. 4058700100051 EN-RSL -> EN-RSL-FW . 4058700100052 CORRECTION The most essential corrections are: 4058700100053 1. On background neutrons with energies higher then 4058700100054 24.5 keV - (1.2+-0.2) % for uranium samples, 4058700100055 (0.6+-0.09) % for B-10. 4058700100056 2. On multiple scattering in samples : 4058700100057 U-233 - (5.6+-0.6)% for 24.5 keV neutrons, 4058700100058 (3.1 +- 0.3) % for thermal neutrons; 4058700100059 U-235 - (5.0 +- 0.5) % for 24.5 keV neutrons, 4058700100060 (2.4 +- 0.2) % for thermal neutrons; 4058700100061 B-10 - (2.4 +- 0.2) % for 24.5 keV neutrons. 4058700100062 3. On resonance selfshielding . 4058700100063 ERR-ANALYS (ERR-T) Total Error - 2.8 %. 4058700100064 STATUS (TABLE) Table of reference. 4058700100065 ENDBIB 63 0 4058700100066 COMMON 8 6 4058700100067 EN EN-RSL-FW MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4058700100068 EN-NRM1 EN-NRM2 4058700100069 KEV KEV B PER-CENT NO-DIM PER-CENT 4058700100070 KEV EV 4058700100071 2.4500E+01 2. 3.521 2.3 9.3700E-01 3.4000E-014058700100072 24.5 0.0253 4058700100073 ENDCOMMON 6 0 4058700100074 ENDSUBENT 73 0 4058700199999 SUBENT 40587002 20090416 41464058700200001 BIB 5 10 4058700200002 REACTION (92-U-233(N,F),,SIG) 4058700200003 SAMPLE Disc of 28.1 mm diameter, U-233 quantity 5.25 gram 4058700200004 MONITOR ((MONIT3)(92-U-233(N,F),,SIG)/(92-U-233(N,TOT),,SIG)) 4058700200005 Ratio of fission / total c-s at thermal energy . 4058700200006 ((MONIT4)(92-U-233(N,F),,NU)//(92-U-233(N,F),,NU)) 4058700200007 Ratio of NU for thermal to Nu for resonance neutrons.4058700200008 MONIT-REF ((MONIT3),H.D.Lemmel,R,IAEA-NDS-1011,1975) 4058700200009 ((MONIT4),J.V.Boldeman+,J,NP/A,265,337,1976) 4058700200010 ERR-ANALYS (ERR-1) Uncertainty of sample weight. 4058700200011 (ERR-2) Uncertainty of B-10 sample weight. 4058700200012 ENDBIB 10 0 4058700200013 COMMON 2 3 4058700200014 ERR-1 ERR-2 4058700200015 PER-CENT PER-CENT 4058700200016 0.5 1.1 4058700200017 ENDCOMMON 3 0 4058700200018 DATA 6 1 4058700200019 DATA ERR-T MONIT3 MONIT3-ERR MONIT4 MONIT4-ERR 4058700200020 B B NO-DIM PER-CENT NO-DIM PER-CENT 4058700200021 2.96 8.0000E-02 9.0200E-01 3.0000E-01 1.0 0.3 4058700200022 ENDDATA 3 0 4058700200023 ENDSUBENT 22 0 4058700299999 SUBENT 40587003 20090416 41464058700300001 BIB 6 11 4058700300002 REACTION (92-U-235(N,F),,SIG) 4058700300003 SAMPLE Disk 27.7 mm diameter, U-235 quantity 5.04 gram 4058700300004 MONITOR ((MONIT3)(92-U-235(N,F),,SIG)/(92-U-235(N,TOT),,SIG)) 4058700300005 Ratio of fission / total c-s at thermal energy . 4058700300006 ((MONIT4)(92-U-235(N,F),,NU)//(92-U-235(N,F),,NU)) 4058700300007 Ratio of NU for thermal to NU for resonance neutrons. 4058700300008 MONIT-REF ((MONIT3),H.D.Lemmel,R,IAEA-NDS-1011,1975) 4058700300009 ((MONIT4),J.V.Boldeman+,J,NP/A,265,337,1976) 4058700300010 ERR-ANALYS (ERR-1) Uncertainty of U-235 sample weight. 4058700300011 (ERR-2) Uncertainty of B-10 sample weight. 4058700300012 HISTORY (20090416A) PAR was deleted from MONIT4 reaction. 4058700300013 ENDBIB 11 0 4058700300014 COMMON 2 3 4058700300015 ERR-1 ERR-2 4058700300016 PER-CENT PER-CENT 4058700300017 0.5 1.1 4058700300018 ENDCOMMON 3 0 4058700300019 DATA 6 1 4058700300020 DATA ERR-T MONIT3 MONIT3-ERR MONIT4 MONIT4-ERR 4058700300021 B B NO-DIM PER-CENT NO-DIM PER-CENT 4058700300022 1.97 6.0000E-02 8.3900E-01 3.0000E-01 1.0 3.0000E-014058700300023 ENDDATA 3 0 4058700300024 ENDSUBENT 23 0 4058700399999 ENDENTRY 3 0 4058799999999